CFD M & S Process for Fast Reactor Fuel Assemblies. Experiments and CDF Code Applications to Nuclear Reactor Safety (XCFD4NRS 2008).

HPamman, K. D. ; Berry, R. A.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear reactors;    Fast reactors;    Fuel assemblies;    Turbulence;    Validation;   

RP-ID  :  DE2008941746

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

A CFD modeling and simulation process for large-scale problems using an arbitrary fast reactor fuel assembly design was evaluated. Three dimensional flow distributions of sodium for several fast reactor fuel assembly pin spacing configurations were simulated on high performance computers using commercial CFD software.